Patent GB-768946-A (GB)
Title: Improvements in and relating to the recovery of uranium values
Inventor: STEDMAN RONALD EDWIN
IPC: C01G43/01
Filed: 1954-02-01
Abstract: Uranium values are recovered from rock phosphate by treating the phosphate with a mineral acid, partially neutralizing the reaction mixture, filtering precipitating from the liquid obtained a uranium salt in the presence of a filter aid using a reducing agent as a precipitant, separating the solids from the liquid and treating the separated solids with a mineral acid to dissolve the precipitated uranium salt from the filter aid and thereafter treating the solution obtained to precipitate uranium values in concentrated form.  The phosphates may be treated with sulphuric, hydrochloric or nitric acid or mixtures thereof or with a mixture of sulphuric acid and ammonium sulphate and the reaction is preferably effected under oxidizing conditions, for example by passing a stream of air through the reaction mixture or by employing nitric acid.  The reaction mixture with or without removable of solids present is then neutralized to a pH of 3.5 to 5 with gaseous ammonia or the hydroxide or carbonate of ammonia, the alkali and alkaline earth metals.  Any solids present after neutralization may be removed by filtering.  A filter aid such as kieselguhr, silica, fuller's earth, or diatomaceous earth suitably in an amount between 0.5 and 1 gm. per litre of liquid is then added after which the uranium values are precipitated by treatment with a reducing agent such as sodium hydrosulphite suitably in a proportion of 0.5 to 1 gm. per litre of liquids. The solids obtained are filtered or settled in which case a part of the thickened slurry may be returned to an earlier step in the process, for example the step preceding precipitation, while the remainder of the slurry is passed to the filtration step.  After filtration the solid is treated with a mineral acid preferably under oxidizing conditions to dissolve the uranium, for example by treatment with sulphuric acid and manganese dioxide, or with nitric acid in excess.  The filter aid recovered may be returned to the process and the liquid obtained may be treated either with an oxidizing agent to precipitate hydrated uranium tetroxide or neutralized to a pH of about 1 with ammonia whereby the uranium is precipitated as uranyl ammonium phosphate.  According to an example a Moroccan rock phosphate containing about one hundred ppm. of uranium, expressed as U3O8 was treated with sulphuric acid and ammonium sulphate at 80 DEG C. while passing a stream of air through the mixture.  Precipitated calcium sulphate was filtered off and sodium silicofluoride removed by the addition of sodium chloride and the pH thereafter adjusted to about 4 by ammonia gas.  The liquor was then filtered to remove sludge, and kieselguhr and sodium hydrosulphite added thereto; the mixture was warmed to 60 DEG C. and was filtered, the retained solid material being then treated with concentrated nitric acid to take the uranium into solution.  The uranium was recovered either by treating with hydrogen peroxide at room temperature to yield on filtering a yellow solid which after drying at 100 DEG C. was recovered as hydrated uranium tetroxide, or alternatively the pH of the liquid was adjusted to 1 by ammonium hydroxide and the mixture stirred whereby a yellow precipitate of uranyl ammonium phosphate was obtained.